ML20214W917

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Forwards Table 1, Cooper Nuclear Station Pressure Isolation Valves, Per Request for Addl Info Re Generic Ltr 87-06
ML20214W917
Person / Time
Site: Cooper Entergy icon.png
Issue date: 06/08/1987
From: Trevors G
NEBRASKA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CNSS877284, GL-87-06, GL-87-6, TAC-64913, NUDOCS 8706160247
Download: ML20214W917 (3)


Text

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GENERAL OFFICE Nebraska Public Power District

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CNSS877284 June 8, 1987 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves - Generic Letter 87-06; Cooper Nuclear Station Docket:

50-298/DPR-46 Gentlemen Pursuant to your request for additional information contained in Generic Letter 87-06, please refer to Attachment A, Table 1,

" Cooper Nuclear Station Pressure Isolation Valves".

. Trevors Division Manager Nuclear Support GAT SSF:jw Attachment cc U.S. Nuclear Regulatory Commission Regional Office, Region IV NRC Resident Inspector Cooper Nuclear Station 8706160247 870600 PDR ADOCK 05000298 P

PDR Y

fD I

~

c-Attachment A.

TABLE 1 COOPER NUCLEAR STATION PRESSURE ISOLATION VALVES LEAK RATE ACCEPTANCE-TEST VALVE DESCRIPTION TEST METHOD CRITERIA FREQUENCY 1.

CS-MO-12A Core Spray Loop A Injection Containment Isolation Appendix J. Type C 1.0 SCFH Once/ Cycle 2.

CS-MO-12B Core Spray Loop B Injection Containment Isolation Appendix J. Type C 1.0 SCFH Once/ Cycle 3.

CS-AO-13A Core Spray Loop A Injection Testable Check Valve Leak Testing Not N/A N/A Performed 4.

CS-AO-13B Core Spray Loop B Injection Testable Check Valve Leak Testing Not N/A N/A Performed 5.

CS-MO-15A Core Spray Loop A Injection Testable Check Valve Leak Testing Not N/A N/A Bypass Performed 6.

CS-MO-15B Core Spray Loop B Injection Testable Check Valve Leak Testing Not N/A N/A Bypass Performed 7.

RHR-MO-25A Residual Heat Removal Loop A Injection Containment Appendix J. Type C 10.0 SCFH Once/ Cycle Isolation 8.

RHR-MO-25B Residual Heat Removal Loop B Injection Containment Appendix J, Type C 10.0 SCFH Once/ Cycle Isolation 9.

RHR-AO-68A Residual Heat Removal Loop A Injection Testable Leak Testing Not N/A N/A Check Valve Performed 10.

RHR-AO-68B Residual Heat Removal Loop B Injection Testable Leak Testing Not N/A N/A Check Valve Performed 11.

RHR-M0-274B Residual Heat Removal Loop A Injection Testable Leak Testing Not-N/A N/A Check Valve Bypass Performed 12.

RHR-MO-274B Residual Heat Removal Loop B Injection Testable Leak Testing Not N/A N/A Check Valve Bypass Performed Page 1 of 2

01 - 1

. Attachment A'.-

v

.i LEAK RATE

~ ACCEPTANCE' TEST.

VALVE' DESCRIPTION TEST METHOD'

CRITERIA"

. FREQUENCY-

13. RHR-MO-17 Residual Heat Removal Inboard Shutdown Cooling

^ Appendix'J. Type.C

4.0;SCFH,

<Once/ Cycle Containment Isolation

14..RHR-MO-18 Residual Heat Removal Outboard Shutdown Cooling Appendix J. Type _C.

'4.0 SCFH

<'Once/ Cycle:

Containment Isolation Page 2'of 2;